ANS / Publications / Journals / Nuclear Technology

Safety System Design Concept and Performance Evaluation for a Long Operating Cycle Simplified Boiling Water Reactor

Kenji Arai, Seijiro Suzuki, Mikihide Nakamaru, Hideaki Heki

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 1-10

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3393

Rapid-L Operator-Free Fast Reactor Concept Without Any Control Rods

Mitsuru Kambe, Hirokazu Tsunoda, Kaichiro Mishima, Takamichi Iwamura

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 11-21

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3394

Performance of Thorium-Based Mixed-Oxide Fuels for the Consumption of Plutonium in Current and Advanced Reactors

Kevan D. Weaver, J. Stephen Herring

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 22-36

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3395

Coolant Mixing in a Pressurized Water Reactor: Deboration Transients, Steam-Line Breaks, and Emergency Core Cooling Injection

Horst-Michael Prasser, Gerhard Grunwald, Thomas Höhne, Sören Kliem, Ulrich Rohde, Frank-Peter Weiss

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 37-56

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3396

Multidimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus During LBLOCA Reflood Phase with a Direct Vessel Injection Mode

Tae-Soon Kwon, Byong-Jo Yun, Dong-Jin Euh, In-Cheol Chu, Chul-Hwa Song

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 57-64

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3397

Experimental Study on the Performance of the Passive Safety Injection in an IIST

Chin-Jang Chang, Chien-Hsiung Lee, Wen-Tang Hong, Lance L. C. Wang

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 65-76

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3398

Stability of Natural-Circulation-Cooled Boiling Water Reactors During Startup: Experimental Results

Annalisa Manera, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 77-88

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3399

Critical Power Correlation for Axially Uniformly Heated Tight-Lattice Bundles

Masatoshi Kureta, Hajime Akimoto

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 89-100

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT143-89

Data Reconciliation in the Steam-Turbine Cycle of a Boiling Water Reactor

Svein Sunde, Øivind Berg, Lennart Dahlberg, Nils-Olof Fridqvist

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 103-124

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3401

Out-of-Phase Boiling Water Reactor Stability Monitoring

Miguel Ceceñas-Falcón, Robert M. Edwards

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 125-131

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3402

Hybrid Reactor Simulation of Boiling Water Reactor Power Oscillations

Zhengyu Huang, Robert M. Edwards

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 132-143

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3403

Optimization of a Boiling Water Reactor Loading Pattern Using an Improved Genetic Algorithm

Yoko Kobayashi, Eitaro Aiyoshi

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 144-151

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3404

Impact of Smoke Exposure on Digital Instrumentation and Control

Tina J. Tanaka, Steven P. Nowlen, Kofi Korsah, Richard T. Wood, Christina E. Antonescu

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 152-160

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3405

Updated Aging Assessment Approach and Use with Electric Cable Insulation

David A. Horvath, R. Paul Colaianni

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 161-170

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3406

Microscopic Void Detection for Predicting Remaining Life in Electric Cable Insulation

David A. Horvath, Steven M. Avila

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 171-179

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3407

A Receding Horizon Controller for the Steam Generator Water Level

Man Gyun Na, Yoon Joon Lee

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 180-196

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3408

Experiences Gained from Independent Assessment in Licensing of Advanced I&C Systems in Nuclear Power Plants

Arndt B. Lindner, Dieter H. Wach

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 197-207

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3409

Performance Evaluation of Fabry-Perot Temperature Sensors in Nuclear Power Plant Measurements

Hanying Liu, Don W. Miller, Joseph W. Talnagi

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 208-216

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3410

A Novel Approach to Process Modeling for Instrument Surveillance and Calibration Verification

Brandon Rasmussen, J. Wesley Hines, Robert E. Uhrig

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 217-226

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3411

Initial Experiments on Fuzzy Control for Nuclear Reactor Operations at the Belgian Reactor 1

Da Ruan

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 227-240

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3412

Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2

Ronald E. Wright, Norman Fletcher, Raymond D. Pearsall, Victor E. Sidnev, John H. Bickel, Aldo Vianello

Nuclear Technology / Volume 143 / Number 2 / August 2003 / Pages 241-245

Technical Note / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3413

Using Point Reactor Models and Genetic Algorithms for On-Line Global Xenon Estimation in Nuclear Reactors

Tunc Aldemir, Giancarlo Torri, Marzio Marseguerra, Enrico Zio, Jeffrey A. Borkowski

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 247-255

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3414

Analysis of Burnup and Economic Potential of Alternative Fuel Materials in Thermal Reactors

Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 256-269

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3415

Maintenance Cycle Extension in the IRIS Advanced Light Water Reactor Plant Design

Mark R. Galvin, Neil E. Todreas, Larry E. Conway

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 270-280

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3416

Safety Analysis of Fast Reactor Core with Uranium-Free Fuel for Actinide Transmutation

Igor Krivitski, Mikhail Vorotyntsev, Valentin Pyshin, Ludmila Korobeinikova

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 281-289

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3417

Step Complexity Measure for Emergency Operating Procedures - Determining Weighting Factors

Jinkyun Park, Wondea Jung, Jaewhan Kim, Jaejoo Ha

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 290-308

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3418

Mobility and Criticality of Plutonium in a Repository

Bernhard Kienzler, Andreas Loida, Werner Maschek, Andrei Rineiski

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 309-321

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3419

Radionuclide Transport in a Multiple and Parallel Fractured System

Chih-Tien Liu, Hund-Der Yeh

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 322-334

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3420

The Effective Diffusion Coefficient of Dissolved Oxygen and Oxidation Rate of Pyrite by Dissolved Oxygen in Compacted Purified and Crude Sodium Bentonites in Carbonate Buffered Solution

Mitsuo Manaka

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 335-346

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3421

Development of Creep Constitutive Equation for Low-Alloy Steel

Kwang J. Jeong, Joon Lim, Il S. Hwang, Hee D. Kim, Martin M. Pilch, Tze Y. Chu

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 347-357

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT03-A3422

Monte Carlo Modeling of the Portuguese Research Reactor Core and Comparison with Experimental Measurements

Ana C. Fernandes, Isabel C. Gonçalves, Nuno P. Barradas, António J. Ramalho

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 358-363

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT03-A3423

Power Profile Evaluation of the JCO Precipitation Vessel Based on the Record of the Gamma-Ray Monitor

Kotaro Tonoike, Takemi Nakamura, Yuichi Yamane, Yoshinori Miyoshi

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 364-372

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT03-A3424